ML20210T219

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Amend 105 to License NPF-51,revising TS Table 4.3-2 to Allow for one-time,five-day Extension of Required Sureillance Interval for Main Steam Isolation Sys Portion of Engineered Safety Feature Actuation Sys Logic
ML20210T219
Person / Time
Site: Palo Verde 
Issue date: 09/04/1997
From: Thomas K
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20210T222 List:
References
NUDOCS 9709150016
Download: ML20210T219 (5)


Text

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NUCLEAR REGULATORY COMMISSION WASHINCTON, D.C. 30606 0001

%.4 * *.. *,6 ARIZONA PUBLIC SERVICE COMPANY. ET AL.

DOCKET NO. STN 50-529 PALO VERDE NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.105 License No. NPF-51 1.

The Nuclear Regulatory Commission (the Comission) has found that:

l A.

The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric Compan Service Company.v. Southern California Edison Company Public of New Mexico. Los Angeles Department of Water and Power, and Southern California Public Power Authority dat?d August 28, 1997, as supplemented by letter dated September 3, 1997, complies with the standards cnd re Energy Act of 1954, as amended (the Act)quirements of the Atomic and the Commi.%1on's regulations set forth in 10 CFR Chapter I:

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulaticiis of the Commission:

C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and ~11) that such activities will be conducted in cTioliance with the Commission's regulations:

D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

-The issuance of this amendment is in accordance with 10 CFR Part 61 of the Comission's regulations and all applicable-requirements

. have been satisfied.

2.

Accordingly, the license is amended by chanW to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-51 is hereby amended to read as follows:

97 M150016 970904 Lh ADOCK 05000S 9

2-(2)

Technical Soecifications and Environmental Protection Plan

- The Technical Specifications contained in Appendix A. as revised through Amendment-No.105, and the Environmental Protection Plan contained in Ap>endix B. are hereby incorporated into this license. APS slall operate the facility in accordance with the Technical Specifications and the Environmental Protection-Plan, except where otherwise stated in specific license conditions.

3.

This license amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION L

WMW Kristine M. Thomas. Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical 4

Specifications Date of Issuance:

September 4, 1997 z

4 81

~.

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 105 TO FACILITY OPERATING LICENSE NO. NPF-51 DOCKET NO. STN 50 529 Replace the following page of the Appent.x A Technical Specifications with the enclosed page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

The corresponding overleaf page is also provided to maintain document completeness.

REMOVE INSERT 3/4 3-3 3/4 3-3 l

l l

.. TABLE'4'3-2-(Continued) i g;

E fjNGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS

5 E

CHANNEL-

' MODES FOR WHICH.,.

CHANNEL -

CHANNEL FUNCTIONAL SURVEILLANCE'

.ESFA SYSTEM FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED-

j 5'

IV.-

MAIN. STEAM LINE ISOLATION-(MSIS)

'A.

Sensor / Trip' Units-1.

Steam Generator Pressure. "

Low S

R

-Q-1.2.3.4

.~

2. -Steam Generator Level - High S

R Q-1.2.3.4 3.

Containment Pressure - High 5

R Q

-1.2.3.4 B.

ESFA System _ Logic m

5-1.

Matrix Logic.

N.A.

N.A.

Q*

1.2.3.4 Y

.- 2.

Initiation Logic N.A.

N.A.

Q*

1.2.3.4' m"

3.

Manual'MSIS N.A.

N.A.

Q*.
1. 2. 3. 4 C.

Automatic 5ctuationLogic

(except subgroup relays)

N.A.

N.A.

Q(2)*

1.2.3.4

-l Actuation Subgroup Relays' N.A.

N.A.

M(1) (3) 1.2.3.4 i!T 8

E

  • These surveillance intervals may be extended on a one-time basis for five days. This provision expires I

on September 9.L1997.

L-___...-.-....

i TABLE 4.3-2 (Continued) s ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUNENTATION SURVEILLANCE REQUIREC NTS 5

  • y, CHANNEL MODES FOR INilCH g

CHANNEL CHANNEL-FUNCTIONAL SURVEILLANCE ESFA SYSTEM FUNCTIONAL UNIT CHECK CALIiWiATION TEST IS REQUIRED m

E V.

RECIRCULATION (RAS)

~.

A.

Sensor / Trip Units m

Refueling Water Storage l

Tank - Low S

R Q

1, 2, 3 -

B.

ESFA System logic 1.

Matrix Logic M.A.

N.A.

Q

1. 2, 3, 4 g

2.

Initiation Logic N.A.

N.A.

Q 1, 2, 3, 4 Y

3.

Manual RAS M.A.

N.A.

Q l

2, 3, 4 0.

Automatic Actuation Logic (except subgroup relays)

N.A.

M.A.

Q(2) 1, 2, 3, 4 Actuation Subgroup Relays N.A.

M.A.

M(1) (3)

I, 2, 3, 4 VI. AUXILIARY FEEDWATER (SG-1)(AFAS-1)

A.

Sensor / Trip Units 1.

Steam Generator #1 Level -

Low 5

R Q

1, 2, 3 l

k 2.

Steam Generator g

& Pressure SG2 > SGI S

R Q

1, 2, 3 l

E

-4 5

_.___-.